ML101750420

Initial Examination Report, No. 50-059/OL-10-02, Texas A&M University AGN-201M Reactor

ML101750420
Person / Time
Site:	Texas A&M University
Issue date:	07/01/2010
From:	Johnny Eads Research and Test Reactors Branch B
To:	Juzaitis R Texas A&M Univ
Doyle P, NRC/NRR/DPR/PRT, 415-1058
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ML101450391	List: ML101450380 ML101750420 ML101750592 ML102371230 ML102420262
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50-059/OL-10-01
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Text

July 1, 2010 Dr. Raymond Juzaitis Nuclear Engineering Department Head Texas A&M University 129F Zachary Engineering Center 3133 TAMU College Station, TX 77843

SUBJECT:

INITIAL EXAMINATION REPORT NO. 50-059/OL-10-01, TEXAS A&M UNIVERSITY AGN-201M REACTOR

Dear Dr. Juzaitis:

During the week of June 14, 2010, the Nuclear Regulatory Commission (NRC) administered an operator licensing examination at your AGN-201m Reactor. The examination was conducted according to NUREG-1478, "Operator Licensing Examiner Standards for Research and Test Reactors," Revision 2. Examination questions and preliminary findings were discussed with those members of your staff identified in the enclosed report at the conclusion of the examination.

In accordance with Title 10 of the Code of Federal Regulations Section 2.390, a copy of this letter and the enclosures will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html. The NRC is forwarding the individual grades to you in a separate letter which will not be released publicly. Should you have any questions concerning this examination, please contact Mr. Paul V. Doyle, Jr, at (301) 415-1058 or via internet e-mail Paul.Doyle@nrc.gov.

Sincerely,

/RA/

Johnny H. Eads, Jr., Chief Research and Test Reactors Oversight Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No.50-059

Enclosures:

1. Initial Examination Report No. 50-059/OL-10-01

2. Written examination with facility comments incorporated cc: without enclosures: See next page

July 1, 2010 Dr. Raymond Juzaitis Nuclear Engineering Department Head Texas A&M University 129F Zachary Engineering Center 3133 TAMU College Station, TX 77843

SUBJECT:

INITIAL EXAMINATION REPORT NO. 50-059/OL-10-01, TEXAS A&M UNIVERSITY AGN-201M REACTOR

Dear Dr. Juzaitis:

During the week of June 14, 2010, the Nuclear Regulatory Commission (NRC) administered an operator licensing examination at your AGN-201m Reactor. The examination was conducted according to NUREG-1478, "Operator Licensing Examiner Standards for Research and Test Reactors," Revision 2. Examination questions and preliminary findings were discussed with those members of your staff identified in the enclosed report at the conclusion of the examination.

In accordance with Title 10 of the Code of Federal Regulations Section 2.390, a copy of this letter and the enclosures will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html. The NRC is forwarding the individual grades to you in a separate letter which will not be released publicly. Should you have any questions concerning this examination, please contact Mr. Paul V. Doyle Jr, at (301) 415-1058 or via internet e-mail Paul.Doyle@nrc.gov.

Sincerely,

/RA/

Johnny Eads, Jr., Chief Research and Test Reactors Oversight Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No.50-059

Enclosures:

1. Initial Examination Report No. 50-059/OL-10-01

2. Written examination with facility comments incorporated cc: without enclosures: See next page DISTRIBUTION w/ encls.:

PUBLIC PROB r/f RidsNRRDPRPRLB RidsNRRDPRPROB Facility File (CRevelle) O-07 F-08 ADAMS ACCESSION #: ML101750420 TEMPLATE #:NRR-074 OFFICE PROB:CE IOLB:LA E PROB:SC NAME PDoyle CRevelle JEads DATE 06/25/2010 06/28/2010 07/1/2010 C = COVER E = COVER & ENCLOSURE N = NO COPY OFFICIAL RECORD COPY

Texas A&M University Docket No. 50-59 cc:

Mayor, City of College Station P.O. Box Drawer 9960 College Station, TX 77840-3575 Governors Budget and Planning Office P.O. Box 13561 Austin, TX 78711 Texas A&M University System ATTN: Dr. Warren D. Reece, Director Nuclear Science Center Texas Engineering Experiment Station F. E. Box 89, M/S 3575 College Station, Texas 77843 Radiation Program Officer Bureau of Radiation Control Dept. Of State Health Services Division for Regulatory Services 1100 West 49th Street, MC 2828 Austin, TX 78756-3189 Susan M. Jablonski Technical Advisor Office of Permitting, Remediation & Registration Texas Commission on Environmental Quality P.O. Box 13087, MS 122 Austin, TX 78711-3087 Test, Research, and Training Reactor Newsletter University of Florida 202 Nuclear Sciences Center Gainesville, FL 32611

U. S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.: 50-059/OL-10-01 FACILITY DOCKET NO.: 50-059 FACILITY LICENSE NO.: R-23 FACILITY: Texas A&M University AGN-201 Reactor EXAMINATION DATES: June 15, 2010 SUBMITTED BY: ___________________________ _________

Paul V. Doyle Jr., Chief Examiner Date

SUMMARY

The NRC administered an operator licensing examination to one Senior Reactor Operator (Instant) candidate. The candidate passed all portions of the examination.

REPORT DETAILS

1. Examiners:

Paul V. Doyle Jr., Chief Examiner, NRC W. Dan Reece, Reactor Supervisor, Texas A&M University Christopher Crouch, Reactor Supervisor in Training Texas A&M Univ.

2. Results:

RO PASS/FAIL SRO PASS/FAIL TOTAL PASS/FAIL Written 0/0 1/0 1/0 Operating Tests 0/0 1/0 1/0 Overall 0/0 1/0 1/0

3. Exit Meeting:

Paul V. Doyle Jr., NRC, Examiner W. Dan Reece, TAMU AGN-201m Reactor Supervisor Christopher Crouch, TAMU, AGN-201m Reactor Supervisor in Training The chief examiner met with the facility staff to discuss the overall administration of the examination. The examiner did not note any serious weaknesses on the part of the candidate.

ENCLOSURE 1

OPERATOR LICENSING EXAMINATION With Answer Key TEXAS A&M UNIVERSITY AGN-201M June 15, 2010 ENCLOSURE 2

Section A Reactor Theory, Thermodynamics and Facility Operating Characteristics Page 1 QUESTION A.01 [2.0 points, 1/2 each]

Match each term in column A with the correct definition in column B.

Column A Column B

a. Prompt Neutron 1. a neutron in equilibrium with its surroundings.

b. Fast Neutron 2. a neutron born directly from fission.

c. Thermal Neutron 3. a neutron born due to decay of a fission product.

d. Delayed Neutron 4. a neutron at an energy level greater than its surroundings.

QUESTION A.02 [1.0 point]

135 Xenon-135 (Xe ) is produced in the reactor by two methods. One is directly from fission; the other is indirectly from the decay of:

136

a. Xe 136

b. Sm 135

c. Cs 135

d. I QUESTION A.03 [1.0 point]

Which of the following does NOT affect the Effective Multiplication Factor (Keff)?

a. The moderator-to-fuel ratio.

b. The physical dimensions of the core.

c. The strength of installed neutron sources.

d. The current time in core life.

QUESTION A.04 [1.0 point]

The neutron interaction in the reactor core that is MOST efficient in thermalizing fast neutrons occurs with the:

a. Hydrogen atoms in the polyethylene molecules

b. Carbon atoms in the polyethylene molecules

c. Uranium atoms in the fuel

d. Oxygen atoms in the fuel

Section A Reactor Theory, Thermodynamics and Facility Operating Characteristics Page 2 QUESTION A.05 [1.0 point]

The total amount of reactivity added by inserting or withdrawing a control rod from a reference height to any other rod height is called?

a. differential rod worth

b. shutdown reactivity

c. integral rod worth

d. reference reactivity QUESTION A.06 [1.0 point]

For most materials the neutron microscopic cross-section for absorption Fa generally

a. increases as neutron energy increases

b. decreases as neutron energy increases

c. increases as target nucleus mass increases

d. decreases as target nucleus mass increases QUESTION A.07 [2.0 points, 1/2 each]

Using the drawing of the Core Rod Position provided, identify each of the following reactivity worths.

a. Total Rod Worth 1. B - A

b. Actual Shutdown Margin 2. C - A

c. Technical Specification Shutdown Margin Limit 3. C - B

d. Excess Reactivity 4. D - C

5. E - C

6. E - D

7. E - A QUESTION A.08 [1.0 point]

Reactor power is rising on a 100 second period. Approximately how long will it take for power to double?

a. 35 seconds

b. 50 seconds

c. 70 seconds

d. 100 seconds

Section B Normal and Emergency Operating Procedures and Radiological Controls Page 3 QUESTION B.01 [2.0 points 1/2 each]

Identify each of the following statements as a Safety Limit (SL), a Limiting Safety System Setting (LSSS) or a Limiting Condition for Operation (LCO).

a. The core thermal fuse shall melt when heated to a temperature of about 120°C resulting in core separation and reactivity loss greater than 5% )k/k.

b. The shutdown margin with the most reactive safety or control rod fully inserted and the fine control rod fully inserted shall be at least 1% )k/k.

c. The maximum core temperature shall not exceed 200°C during either steady-state or transient operation.

d. The reactor room and accelerator room shall be considered a restricted area whenever the reactor is not secured.

QUESTION B.02 [1.0 point, 1/4 each]

Identify whether each of the experiments listed below is Allowed (AL), required Double Encapsulation (DE), or is not allowed (NA) by technical specifications.

a. An experiment containing 22 grams of explosive material.

b. An experiment containing liquid fissionable material.

c. An experiment, the radioactive material content, including fission products of any experiment shall be limited so that the complete release of all gaseous, particulate, or volatile components from the experiment will not result in doses in excess of 10% of the equivalent annual doses stated in 10 CFR Part 20 for persons occupying (1) unrestricted areas continuously for two hours starting at time of release or (2) restricted areas during the length of time required to evacuate the restricted area.

d. An experiment containing a material corrosive to reactor components.

QUESTION B.03 [1.0 point, 1/4 each]

Identify each of the following evolutions as either a channel check (CHECK), a channel test (TEST), or a channel calibration (CAL).

a. You hold a known source up to a portable ion chamber radiation monitor to meter movement (not a proper value).

b. You observe that the countrate channel and the log channel are tracking power together.

c. You irradiated a gold foil at 5 watts, three days ago. You are in the process of evaluating the foil to determine whether adjustments to the instrumentation must be made.

d. You insert a 60 Hz signal into an instrument channel to verify a meter reads a proper value.

Section B Normal and Emergency Operating Procedures and Radiological Controls Page 4 QUESTION B.04 [1.0 point]

According to Technical Specification 3.4.d the reactor room shall be considered to be a HIGH RADIATION area whenever reactor is operated at a power level equal to or greater than ?

a. 0.3 watts

b. 0.6 watts

c. 0.9 watts

d. 1.2 watts QUESTION B.05 [1.0 point]

Given a 1 cm (0.394 inch) thick lead shield reduces the dose rate from an experiment by a factor of 2. A 10 cm (3.94 inch) thick shield will reduce the dose by a factor of approximately

a. 4

b. 20

c. 100

d. 1000 QUESTION B.06 [1.0 point]

Of the following, who is allowed to operate the controls of the reactor under your direction?

a. A local college newspaper reporter who wants to write a story on the safety of nuclear reactors.

b. A new student participating in a nuclear engineering laboratory course.

c. A health physicist who is trying to gain a certified health physicist (CHP) license.

d. An NRC inspector trying to make sure that all set points of the reactor are the same as those in the technical specifications.

QUESTION B.07 [1.0 point]

The dose rate from a mixed beta-gamma point source is 100 mrem/hour at a distance of one (1) foot, and is 0.1 mrem/hour at a distance of twenty (20) feet. What percentage of the source consists of beta radiation?

a. 20%

b. 40%

c. 60%

d. 80%

Section B Normal and Emergency Operating Procedures and Radiological Controls Page 5 QUESTION B.08 [1.0 point, 1/4 each]

Match the Operator License requirement (from 10 CFR 55) in Column A with the proper time period from column B.

Column A Column B

a. License Renewal 1 year

b. Medical Examination 2 years

c. Requalification Written 4 years

d. Requalification Operating Test 6 years QUESTION B.09 [1.0 point]

Given the following information, calculate the half-life of the sample. (Show all calculations.)

Time (in minutes) Counts per minute 0 900 30 740 60 615 90 512 180 294

a. 551 minutes

b. 312 minutes

c. 111 minutes

d. 88 minutes

Section C Facility and Radiation Monitoring Systems Page 6 QUESTION C.01 [1.0 point]

Which ONE of the below listed scrams is designed to prevent excessive radiation levels?

a. low reactor period

b. low water temperature

c. low water level

d. high count rate QUESTION C.02 [1.0 point]

The Low Level Interlock is NOT controlled by power level indication from the:

a. Countrate Channel

b. Log Channel.

c. Linear Channel.

d. Skirt Monitor channel.

QUESTION C.03 [2.0 points, 0.4 each]

Match the purpose in column A with the correct material from column B.

Column A Column B

a. fast neutron shield 1. Lead

b. reflector 2. Graphite

c. gamma-ray shield 3. Beryllium

d. moderator in core 4. Aluminum

e. moderator in fuse 5. Polyethylene

6. Polystyrene

7. Water

Section C Facility and Radiation Monitoring Systems Page 7 QUESTION C.04 [1.0 point]

Emergency Procedure PE-3 Radioactive Contamination of Personnel or Spill of Radioactive Material, states If radioactive spill enters sanitary drain system, shut off power to sanitary drain sump pumps. Where would you go to de-energize the sanitary drain sump pumps?

a. On the reactor room wall behind the operator (east wall).

b. On the reactor room wall behind the reactor (west wall)

c. On the corridor wall just outside the door to the reactor room.

d. In the room with the door to access the controlled area, on the south wall.

QUESTION C.05 [1.0 point]

Which ONE of the following is NOT an interlock preventing rod insertion?

a. Both safety rods must be fully inserted prior to inserting the coarse control rod.

b. Both safety rods must be fully inserted prior to inserting the fine control rod.

c. The coarse control rod must be fully withdrawn prior to inserting the safety rods.

d. The fine control rod must be greater than or equal to half inserted prior to inserting the safety rods.

QUESTION C.06 [1.0 point]

Which one of the design features listed below insures that the thermal fuse melts before the rest of the reactor core? The thermal fuse

a. fuel has a higher density of fuel pellets as the rest of the core.

235 238

b. fuel has a higher ratio of U to U atoms as the rest of the core.

c. moderator has a higher density of polyethylene as the rest of the core.

d. moderator has a lesser density of polystyrene as the rest of the core.

QUESTION C.07 [1.0 point]

Which ONE control or safety rod listed below will NOT instantaneously eject from the core in the event of a SCRAM?

a. Coarse.

b. Fine.

c. Safety 1.

d. Safety 2.

Section C Facility and Radiation Monitoring Systems Page 8 QUESTION C.08 [1.0 point]

Which ONE of the following provides the motive force for control and safety rod withdrawal during a SCRAM?

a. Gravity

b. Gravity and Air pressure

c. Fast Motor

d. Gravity and spring.

QUESTION C.09 [1.0 point]

What material is typically placed in the glory hole to ensure the reactor stays in a sub-critical mode when no one is present?

a. Beryllium.

b. Boron.

c. Cadmium.

d. Polyethylene.

Section A Reactor Theory, Thermodynamics and Facility Operating Characteristics Page 9 A.01 a, 2; b, 4; c, 1 d, 3 REF: (Reference 1), Vol. 1, Module 2, Paragraph Neutron Slowing Down and Thermalization on pg. 23, also Paragraph Neutron Classification on pg. 29.

A.02 d REF: (Reference 1), Vol. II, Module 3, Paragraph Production and Removal of Xenon-135 on pg. 34.

A.03 c REF: (Reference 1), Vol. II, Module 3, see heading Six Factor Formula discussion on pages. 12 & 13.

A.04 a REF: (Reference 1), Vol. I, Module 2, see heading Neutron Slowing Down and Thermalization top of pg. 24.

A.05 a REF: (Reference 1), Vol. II, Module 3, see heading Integral and Differential Rod Worths discussion on pages 51 through 56.

A.06 b nd REF: (Reference 1), Vol. I, Module 2, 2 ¶ on page 9.

A.07 a, 7; b, 5; c, 6; d, 2 REF: Standard NRC Question A.08 c t/T REF: P = P0 e --> ln(2) = time ÷ 100 seconds -> time = ln (2) x 100 sec. 0.693 x 100 0.7 x 100 70 sec.

Reference 1 = DOE Handbook Nuclear Physics and Reactor Theory, Volumes I and II.

Section B Normal and Emergency Operating Procedures and Radiological Controls Page 10 B.01 a, LSSS; b, LCO; c, SL; d, LCO REF: Technical Specifications §§ 2.2, 3,1(b), 2.1 and 3.4.

B.02 a, NA; b, DE; c, AL; d, DE REF: Technical Specifications §§ 3.3(b), 3.3.(a), 3.3.c(1) and 3.3(b)

B.03 a, CHECK; b, CHECK; c, CAL; d, TEST REF: Technical Specifications 1.1, 1.2, and 1.3 B.04 c REF: Technical Specification 3.4.d B.05 d 10 REF: 2 = 1024 . 1000 B.06 b REF: 10CFR55.13 B.07 c REF: 10CFR20. At 20 feet, there is no beta radiation. Gamma at 20 feet = 0.1 mrem/hour, gamma at 1 foot =

40 mrem/hour. Therefore beta at 1 foot = 60 mrem/hour = 60%.

B.08 a, 6; b, 2; c, 2; d, 1 REF: 10CFR55.59 B.09 c t (H180)

REF: A = A0 e , 294 = 900 e , [ln(294/900)] / 180 = = 0.0062156389. t1/2 = ln(2)/ = 111.517

Section C Facility and Radiation Monitoring Systems Page 11 C.01 c REF:

C.02 d REF: (SAR) § 7.2.3 3rd ¶ under Channel #2.

C.03 a, 7; b, 2; c, 1; d, 5; e, 6; REF: ISU, Safety Analysis Report (SAR), § 4.2, Table 4.2-1 C.04 d REF: Emergency Procedure PE-3, Radioactive Contamination of Personnel or Spill of Radioactive Material within Reactor Facility C.5.

C.05 d rd REF: TAMU SAR § 7.3 & 4, Reactor Control and Protective Systems 3 ¶ C.06 a REF: TAMU SAR § 4, table 4.2-1, part B Fuel.

C.07 b REF: NRC Examination Question Bank, also TAMU SAR Top of page 4-10.

C.08 d nd rd REF: TAMU SAR § 3.1 2 ¶, 3 sentence.

C.09 c REF: Standard Operating Procedures § 3.6.4 Securing

U. S. NUCLEAR REGULATORY COMMISSION RESEARCH AND TEST REACTOR OPERATOR LICENSE EXAMINATION FACILITY: Texas A&M University REACTOR TYPE: AGN-201M DATE ADMINISTERED: 06/ /2010 CANDIDATE:

INSTRUCTIONS TO CANDIDATE:

Answers are to be written on the answer sheet provided. Attach the answer sheets to the examination.

Points for each question are indicated in brackets for each question. A 70% in each section is required to pass the examination. Examinations will be picked up three (3) hours after the examination starts.

% of Category  % of Candidates Category Value Total Score Value Category 10.00 33.3 A. Reactor Theory, Thermodynamics and Facility Operating Characteristics 10.00 33.3 B. Normal, Emergency and Radiological Controls Procedures 10.00 33.3 C. Facility and Radiation Monitoring Systems 30.00  % TOTALS FINAL GRADE All work done on this examination is my own. I have neither given nor received aid.

Candidate's Signature

NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the following rules apply:

1. Cheating on the examination means an automatic denial of your application and could result in more severe penalties.

2. After the examination has been completed, you must sign the statement on the cover sheet indicating that the work is your own and you have neither received nor given assistance in completing the examination. This must be done after you complete the examination.

3. Restroom trips are to be limited and only one candidate at a time may leave. You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.

4. Use black ink or dark pencil only to facilitate legible reproductions.

5. Print your name in the blank provided in the upper right-hand corner of the examination cover sheet and each answer sheet.

6. Mark your answers on the answer sheet provided. USE ONLY THE PAPER PROVIDED AND DO NOT WRITE ON THE BACK SIDE OF THE PAGE.

7. The point value for each question is indicated in [brackets] after the question.

8. If the intent of a question is unclear, ask questions of the examiner only.

9. When turning in your examination, assemble the completed examination with examination questions, examination aids and answer sheets. In addition turn in all scrap paper.

10. Ensure all information you wish to have evaluated as part of your answer is on your answer sheet.

Scrap paper will be disposed of immediately following the examination.

11. To pass the examination you must achieve a grade of 70 percent or greater in each category.

12. There is a time limit of three (3) hours for completion of the examination.

13. When you have completed and turned in you examination, leave the examination area. If you are observed in this area while the examination is still in progress, your license may be denied or revoked.

Section A: Theory, Thermodynamics & Facility Operating Characteristics Page 1 A.01a 1 2 3 4 ___ A.05 a b c d ___

A.01b 1 2 3 4 ___ A.06 a b c d ___

A.01c 1 2 3 4 ___ A.07a 1 2 3 4 5 6 7 ___

A.01d 1 2 3 4 ___ A.07b 1 2 3 4 5 6 7 ___

A.02 a b c d ___ A.07c 1 2 3 4 5 6 7 ___

A.03 a b c d ___ A.07d 1 2 3 4 5 6 7 ___

A.04 a b c d ___ A.08 a b c d ___

Section B: Normal, Emergency & Radiological Controls Procedures Page 2 B.01a SL LSSS LCO ___ B.03d CHECK TEST CAL ___

B.01b SL LSSS LCO ___ B.04 a b c d ___

B.01c SL LSSS LCO ___ B.05 a b c d ___

B.01d SL LSSS LCO ___ B.06 a b c d ___

B.02a AL DE NA ___ B.07 a b c d ___

B.02b AL DE NA ___ B.08a 1 2 4 6 ___

B.02c AL DE NA ___ B.08b 1 2 4 6 ___

B.02d AL DE NA ___ B.08c 1 2 4 6 ___

B.03a CHECK TEST CAL ___ B.08d 1 2 4 6 ___

B.03b CHECK TEST CAL ___ B.09 a b c d ___

B.03c CHECK TEST CAL ___

Section C Facility and Radiation Protection Systems Page 3 C.01 a b c d ___ C.04 a b c d ___

C.02 a b c d ___ C.05 a b c d ___

C.03a 1 2 3 4 5 6 7 ___ C.06 a b c d ___

C.03b 1 2 3 4 5 6 7 ___ C.07 a b c d ___

C.03c 1 2 3 4 5 6 7 ___ C.08 a b c d ___

C.03d 1 2 3 4 5 6 7 ___ C.09 a b c d ___

C.03e 1 2 3 4 5 6 7 ___

EQUATION SHEET

( )2 eff = 0.1sec 1 Q& = m& c P T = m& H =UAT Pmax =

(2 l )

t P = P0 e S S SCR = l* =1x10 4 sec 1 K eff eff + &

SUR = 26 .06

( ) (

CR1 1 K eff1 = CR2 1 K eff 2 ) CR1 ( 1 ) = CR2 ( 2 )

(1 ) M=

1

= 2 CR P = P0 10SUR(t )

P= P0 1 K eff CR1 1 K eff1 1 K eff l*

M= SDM = =

1 K eff 2 K eff l* 0.693 K eff 2 K eff1

+ T1 =

eff + & 2 K eff1 K eff 2 K eff 1

= DR = DR0 e t 2 DR1 d1 = DR2 d 2 2

K eff 6 Ci E (n ) ( 2 )2 = (1 )2 DR =

R2 Peak2 Peak1 6

( 2.3x10 yr )

DR - Rem, Ci - curies, E - Mev, R - feet 135 52Te (19 sec) 135 ( 6.6 hr ) 135 ( 9.1 hr ) 135 53 I 54 Xe 55 Cs 56 Ba 135 1 Curie = 3.7 x 1010 dis/sec 1 kg = 2.21 lbm 1 Horsepower = 2.54 x 103 BTU/hr 1 Mw = 3.41 x 106 BTU/hr 1 BTU = 778 ft-lbf EF = 9/5 EC + 32 1 gal (H2O) . 8 lbm EC = 5/9 (EF - 32) cP = 1.0 BTU/hr/lbm/EF cp = 1 cal/sec/gm/EC

All Control Elements in Bank Position Simplified Drawing Reactor Core at Cold Critical Note: Bank position means all rods are at the with all rods banked same core height, which is impossible for an AGN reactor operating correctly.

E: Top of Control Elements D: Bottom of Core plus or less worth of most reactive blade C: Bottom of Reactor Core B: Bottom of Core plus or less worth of most reactive blade A: Bottom of Control Elements